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Probabilistic Structural Mechanics Analysis of the Degraded Davis-Besse RPV Head

[+] Author Affiliations
Paul T. Williams, Shengjun (Sean) Yin, B. Richard Bass

Oak Ridge National Laboratory, Oak Ridge, TN

Paper No. PVP2006-ICPVT-11-93270, pp. 479-488; 10 pages
doi:10.1115/PVP2006-ICPVT-11-93270
From:
  • ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
  • Volume 3: Design and Analysis
  • Vancouver, BC, Canada, July 23–27, 2006
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4754-3 | eISBN: 0-7918-3782-3
  • Copyright © 2006 by ASME

abstract

The Heavy-Section Steel Technology (HSST) Program at Oak Ridge National Laboratory (ORNL) performed a probabilistic structural mechanics (PSM) analysis of the damaged Davis Besse reactor pressure vessel head in support of the United States Nuclear Regulatory Commission’s ongoing forensic investigations. This paper presents a summary of the results of that PSM analysis, including a description of the Davis-Besse wastage-area damage model, the technical basis for the model, and the results of sensitivity studies based on a cladding capacity analysis (CCA) and an Accident Sequence Precursor (ASP) investigation of the wastage cavity. A companion paper describes the HSST experimental program carried out at ORNL in parallel with the PSM analysis.

Copyright © 2006 by ASME

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